ML20076D131

Rev 3 to Interface Control Agreement,Westinghouse Piping & Structural Evaluation Program for Byron Station Unit 1

ML20076D131
Person / Time
Site:	Byron, LaSalle, 05000000
Issue date:	10/29/1982
From:	COMMONWEALTH EDISON CO., SARGENT & LUNDY, INC., WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20076C924	List: ML20076C922 ML20076C992 ML20076D015 ML20076D046 ML20076D074 ML20076D111 ML20076D131 ML20076D135 ML20076D144 ML20076D148
References
NUDOCS 8305200681
Download: ML20076D131 (19)

Text

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• EwkM A CAW 5026 Westinghouse Water Reactor Nataf Connemat Electric Corporation Divisions bra m Dw n Ecz355 PittstisgiPenrelvania 15233 November 29, 1982

.Mr. J. D. Deress .

Project Engineering Manager File: CAE 2.1.186 Byron & Braidwood Projects . EMXP-1000 Commonwealth Edison Company .

P. O. Box 767 ,

Chicago, IL 60690 COMMONWEALTH EDISON COMPANY BYRON STATION - UNIT 1 Rev. 3, Piping Interface Control Agreement

Dear Mr.' Deress:

Enclosed for your use is a copy of the approved Interface Control Agreement Westinghouse Piping and Structural Evaluation Program for the Byron Station Unit 1 - Rev. 3 dated October 29, 1982.

Changes incorporated into Rev. 3 are identified by the number 3 on the right hand margin of the applicable pages.

If you have any questions concerning the agreement, please don't hesitate to call.

Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION

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W. E. Kort Manage Commonwealth Edison Projects FCDiAgostino/ deb J. D. Deress 2L, 2A cc: W. C. Cleff 2L, 2A 8305200681 830511 p DR ADOCK 05000373 PDR

,.. o INTERFACE C0tiTROL AGREEME;;T .

WESTIi4GHOUSE PIPING AliD STRUCTURAL EVALUATION FF.C37.AM FOR THE BYRCN STATION UNIT 1 October 13, 1980 The provisions of this document have been reviewed and agreed

- upon by each of the undersigned part1Ts, l

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Rev. 3,10/29/82 l

,- e TABLE OF CONTENTS SECTION TITLE PAGE ,

1.0 INTRODUCTION

1 2.0 SCOPE 2 3.0 DEFINITIONS 3 .

4.0 ORGANIZATION 3 5.0 RESPONSIBILITIES 3 -

6.0 PROJECT CORRESPONDENCE 4 7.0 INTERFACE PROCEDURE DESCRIPTIONS 5

8.0 REFERENCES

5 Appendix 1 INTERFACE RESPONSiBILTY MATRICES 6 Appendix 2 BASELINE DOCUMENT REFERENCE 12 3

Appendix 3 INTERFACE CONTROL AGREEMENT ADDENDUM - SITE 13 PP e

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FIGURES NO. TITLE PAGE 1 PIPING RESPONSIBILITY MATRIX 7 2 SUPPORT RESPONSIBILITY MATRIX 9 3 DESIGN DOCUMENT RESPONSIBILITIES 10 I

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WESTINGHOUSE PIPlNG AND STRUCT11RAL EVALUATION PROCRAM FOR THE BYRON STATION UNIT 1

1.0 INTRODUCTION

The purpose of this Interface Control Agreement is to define the relationship between the participating work groups and to describe how the Westinghouse Structural and Equiprent Engineering Department wlIl provide

. engineering required for the analysis and qualification of the piping and piping structures within its defined scope as delineated in Section 2. To perform this analysis, the Structural and Equipment Enigineering Department has elected to provide engineers and technicians to perf orm this work in the engineering of fices in Pittsburgh, Pennsylvania, Schaumburg, 3 lilinois, and at the Byron site. All of the engineers and technicians assigned to this project are under the cognizance of the Westinghouse Nuclear Technology Division, Structural and Equipment Engineering Department.

Work is performed under this program to assure that (a) the analysis and (b) the as-built configuration of the piping and support systems are correct as shown by appropriate documentation, i.e final isometric drawings for piping systems, approved structural design drawings for piping supports.

The piping analysis and piping support design work being performed by Westinghouse is a continuation of the design effort initially performed by Sargent & Lundy Engineers. The Westinghouse engineering work initially is based on the controlled project documents that were In place at the flee of the transf er of the piping analysis work from Sargent & Lundy to Westinghouse. This controlled Information includes the S & L single line piping drawings and the support structure drewings in existence when Westinghouse commenced its engineering effort. In order to achieve more realistic description of the piping systems and analysis, it has been agreed that Commonwealth Edison (CECO) will supply to Westinghouse as controlled" design Information 'the f abrication isometric drawings which will then become the controlled input.for the piping qualification.

The piping analysis performed by Westinghouse is done using automated Interactive graphics piping analysis methods. These methods use mini-computers both at the Byron site and at the Structural and Equipment Engineering Department offices in Pittsburgh, Pennsylvania and Schaumburg, 3 tilinois. The piping engineer (either at the site or office) develops piping models directly from the febrication isometric drewings using the mini-computer Interactive graphics system. Upon completelon of the analysis models, an engineering check is performed by an engineer that did not participate in the formulation of the ptrticular model.

l ' The analysis then proceeds by transferring the mini-computer informetton to l the Westinghouse CDC 7600 or the CRAY computers in Pittsburgh. The results 3

( of this analysis provide piping stress levels and piping support loads.

Upon achieving a satisfactory piping and support configuration, the piping support loads are provided to the piping support designers.

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2 The piping supports previously designed by Sergent & Lundy are verified to see if they are capable of supporting the loads generated by the piping analysis. If so, the drawings are released for f abrication as. Westinghouse drawings, if not, the piping support drawings are modified to reflect design changes. In the event that new support designs are required, these 3 are made by the piping design group and original drawings prepared. When the drawing revisions or initial work of support drawings are approved, they are transmitted in accordance with the distribution needs for Commonwealth Edison through the Westinghouse Project Department Of fice.

The work process described above is independent of geographical location and is performed through the use of dedicated computers using interactive graphics techniques. The work location at the site, entitled the Westinghouse Structural Analysis Mobile Unit (SAMU) is directly coupled to 3 the Pittsburgh and Midwest Nuclear Technology Center (MNTC) computers through dedicated data lines. Piping analysis functions can, therefore, be performed independently of geographical location by accessing the isometric models contained in computer memory. Support design also is performed independently of geographical location.

Westinghouse will provide the analysis to as-built piping and piping support conditions supplied to us by CECO. As part of the permanent records for the site, Westinghouse w!!! provide the certified stress reports for the piping and support structures. Additionally, Isometric drawings reflectTng the as-analyzed geometry will be drawn by computer

, driven drafting machines as part of the stress reports.

Information regarding job status can be obtained in Pittsburgh, MNTC, or SAMU by accessing the Westinghouse computer network.

2.0 SCOPE -

This interf ace agreement applies to the following wer k in the Westinghouse Scope of Supply.

The analysis and qualification (e.g verification that the results cf the analysis are within Code allowables) of Class A, B, C, and D piping (ANS Safety Class I, 2, 3, and Non-Nuclear Safety respectively) systems within the Containment Building and the Auxiliary Building for the Byron Unit I station. The scope includes all lines in the Containment Building except as noted below, in addition, the scope includes four systems (CY, CS, Si, and RH plus additional coupled piping necessa,ry to adequately evaluate these four systems) in the Auxiliary Building plus most of the piping within Area 5 of the Auxiliary Building for a total of approximately 550 large and small 3 bore piping systems. This includes the associated design and qualification for the piping supports and restraints. The only piping and support systems specifically excluded from this document are (1) the Reactor Coolant Loop, (2) the primary equipment component supports, (3) containment spray piping systems ICS01 and ICS02, and (4) the Component Cooling, Fire Protection, and Service Water systems in Area 5. The Westinghouse scope in the Auxiliary Building is defined by the baseline document identified in Appendix 2.

3 All containment piping and supports will be analyzed and qualified in accordance with the requirements of Section III of the 1977 ASME Boiler and Pressure Vessel Code, through Sumer 1979 Addenda. In addition, all supports for containment piping systems will be desinged in accordance with Section III of the 1977 ASME Code, Summer 1979 Addenda. This scoce of the

, applicability of the Codes referenced in this paragraph does not apply to the installation and fabrication of the' piping and supports.

3.0 DEFINITIONS Enaineerino Chance Notice (ECN). A procedure for changing Design Drawings within the Westingnouse Scope as described in this agreement.

Field Chance Recuest (FCR). A procedure for controlling field changes initiated by Comonwealth Edison Company.

4.0 ORGANIZATION 4.1 For the Piping and Structural Evaluation Program, Westinghouse Electric Corporation is represented by the Nuclear Operations Division (N0D) Projects Department and Nuclear Technology Division (NTD)

Structural and Equipment Engineering Department and the Nuclear Technology Division Product Assurance Department. Westinghouse NOD is located at the Monroeville Nuclear Center, Pittsburgh, Pennsylvania.

The NTD Product Assurance Department is based at the Penn Center Site in Pittsburgh, Pennsylvania, and the NTD Structural and Equipment Engineering Department is located in Pittsburgh, Pennsylvania, with satellite offices in Tampa, Florida, and Schaumburg, Illinois. The 3 Westinghouse Structural Analysis Mobile Unit located at the Byron Site is a satellite office of the Structural and Equipment Engineering Department.

l The Westinghouse organization is formally described in WCAP 8370, l Section 17.1.1 and changes are distributed to controlled manual l holders.

4.2 Sargent & Lundy Engineers, Chicago, Illinois, is represented by the Project Management Division.

4.3 Commonwealth Edison Company (CECO) is represented by the Byron Engineering Organization and the Byron Site Construction Organization.

The Byron Project Engineering Organization, as the Owner, has the overall responsibility for the activities described in this agreement.

5.0 RESPONSIBILITIES

• 5.1 Piping Qualification The responsibilities for each phase of work associated with piping 3 l

analysis and stress qualification are shown in Appendix 1, Figure 1.

This chart lists the various piping analysis tasks and shows organizational responsibility for each work item associated with the analysis and qualification of the piping system.

.- . 4 5.2 Support Design and Qualification The responsiblities for each phase of work associated with support and pipe whip restraints design and qualification are shown in Appendix 1, Figure 2. This chart defines the responsibility for each 3 work item associated with the design and qualification of piping system supports.

5.3 Quality Assurance The responsibilities for Quality Assurance and issuance of design documents for this project are shown in Appendix 1, Figure 3. 3 The Quality Assurance Program for Westinghouse activities at Westinghouse locations is defined by the current revision of the following documents.

WCAP 8370 WRD Quality Assurance Plan WCAP 9550 WRD NSSS Policies and Procedures Manual WCAP 9615 NTD ASME Quality Assurance Manual WCAP 9565 NTD Design Control Manual WCAP 8654 Quality Assurance Records Documentation Plan

, WCAP 9805 SEED Policies and Procedures Manual The latest revisions are applicable and available at the W satellite office located at the plant site.

QA records will follow the, procedure of F2702 and WCAP 8654.

( 5.4 Westinghouse Structural Analysis Mobile Unit (W SAMU)

The Westinghouse Structural Analysis Mobile Unit is an extension of the Westinghouse Structural and Equipment Engineering Department located in Pittsburgh, Pennsylvania. The activities of the W SAMU are managed by the W manager assigned to the SAMU facility and provide Design activities under the procedures in Section 5.3.

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6.0 PROJECT CORRESPONDENCE

• 6.1 All project correspondence from Westinghouse shall be through the W N00 Project Department in accordance with the Byron project Distribution listing.

6.2 All project correspondence form Sargent & Lundy will be controlled by the S & L Project Management Division.

6.3 All project correspordence from Commonwealth Edison shall be through Project Engineering Organization or Byron Site Construction as-appropriate.

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7.0 INTERFACE PROCEDURE DESCRIPTIONS Procedures prescribing the activities described in this agreement are contained in the documents listed in Section 5.3 and SEED 1.4 entitled Engineering Change Notica and SEED 1.5 Field Change Requests. -

The latest revisions of these procedures are applicable and available at the 1 SAMU office. Unless specified otherwise in this agreement, all design documents distributed by Westinghouse shall be distributed through the NOD P.ojects Department.

7.1 Engineering Change Notices (ECN)

ECN's issued by Westinghouse will be in accordance with the Westinghouse procedure SEED 1.4.

7.2 Field Change Requests (FCR)

All FCR's issued by Commonwealth Edison will be in accordance with CECO procedure QF 3.2 and E is considered the AE with respect to action required within the scope of QP 3.2.

7.3 Support Design Drawing The standard distribution for support drewings shall be In accordance with the controlled distribution list maintained bi X NOD Projects Department.

7.4 Piping Isometric Drawings Piping Isometric drawings whall be issued to the E SAMJ of fice by FCR and from Commonwealth Edison Construc*lon as design input for X piping 3 analysis. -

7.5 Other Engineering Documentation E Engineering documents and reports will be issued as required by X NOD Projects Department.

8.0 REFERENCES

8.1 X INTERNAL DOCUMENT 3 WCAP 8370 WRD Quality Assurance Plan WCAP 8654 Quality Assurance Records Documentation Plan '

WCAP 9550 WRD NSSS Policies and Procedures Manual WCAP 9565 NTD Design Control Manual WCAP 9625 NTD ASME Quality Assurance Manual WCAP 9805 SEED Policies and Procedures Manual 8.2 SUPPLEMENTARY DOCUEPHTS Interf ace Control Agreement Supplement between Westinghouse 3 SAMU-1, NPS, CECO, and S&L. Rev. 1.

6 APPENDIX 1

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INTERFACE RESPONSIBILITY MATRICES Figure 1 - Piping Responsibility Matrix Figure 2 - Support Responsibility Matrix 3 Figure 3 - Design Document esponsibility LEGEND C -

Commonwealth Edison Company S -

Sargent & Lundy Corporation W -

Westinghouse Electric Corporation w

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7 Appendix 1 FIGURE 1 5

BYRON UNIT 1 PIPING RESPONSIBILITY MATRIX CLASS CLASS CLASS CLASS NO. ACTIVITY A B C D 1 Qualification Analysis W W W W 2 Certified Stress Report W W W N/A 3 Third Party Review of Certified Stress Report W W W N/A 4 Specify High Energy Pipe Break Locations W W W W 5 Specify Pipe Support Loadings W W W W l3 6 Provide Overpressurization Protection Report W W W N/A 7 Provide Thermal / Hydraulic Parameters for Penetration Analysis W W W W 8 Specify Pipe Mechanical Loadings at Penetrations W W W W 9 Provide MS & FW Hydraulic Forcing 3

Functions W W W W 10 Provide Allowable Nozzle Loads for X Equipment W W W y 11 Provide Allowable Nozzle Loads for Non-M Equipment S S S , S 12 ' Provide Seismic Response Spectra S S S S 13 Provide Anchor Motions ai all Penetrations S S S S

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8 14 Provide Certifled E-Specs for X Equipment W W W W 15 Provide Certified E-Specs for Non-H Equipment S s 3 3

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Appendix 1 FIGURE 2 BYRON UNIT 1 SUPPORT RESPONSIB1 LIT ( MATRIX CLASS CLASS CLASS CLASS NO. ACTIVITY A B C D 1 PIPE SUPPORT DESIGN W W W W 2 PIPE SUPPORT ANALYSIS W W W W 3 CERTIFIED STRESS REPORT W W W N/A l 3 PIPE WHIP RESTRAINT DESIGN & ANALYSIS W/S W/S W/S W/S 4 l3 5 PROVIDE LOADING AT PIPE SUPPORT BASE PLATES, EMEDS, & STRUCTURAL STEEL ATTACHMENTS W W W W QU l C bF AS kT W W W W l3 7 PROVIDE DESIGN, ANALYSIS, &

QUALIFICATION OF EEEDS, AND SUPPORTING STRUCTURAL STEEL OR CONCRETE S S S S l3 8 PROYlDE DESIGN, ANALYSIS &

CERTIFIED STRESS REPORT FOR ALL PRIMARY CONTAINMENT S S S S 3 PENETRATIONS 10 RELEASE SUPPORT DRAWINGS FOR W W W y FABRICATION l

11 THIRD PARTY REVIEW OF CERTIFIED

. STRESS REPORT W W W ,

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Appendix 1 '

FIGURE 3 BYRCN UNIT 1 .

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DESIGN DOCUPENT RESPONSIBILITES CLASS CLASS CLASS CLASS NO. ACTIVITY A B C D 1 Piping and Support Design Specifications W W W N/A 2 Piping and Support Fabrication Specifications S S S S 3 Piping and Support installation Specifications S S S S 4 QA Review of Westinghouse Design Specifications W W F W 5 Code Data Reports C C C N/A 6 QA Audit of Westinghouse Design Activitgs W W W W 7 initiate Applicable Field Chan'ge Requests C C C C S Review and Resolve Applicable Field Change Requests W W W W 9 initiate Westinghouse Engineering Change Notices (ECN) W W W W 10 Provide Non-Westinghouse Equipment Draw ings S S S S 11 Provide Listings of Initial Design Drawings, Line Numters, Yalves, Supports, Components S S S S 12 Provide ' As-Built' Meesuroments of Piping System and Supports, including Geometry, Location, and Orientation C C C C

11 FIGURE 3 (Con't)

CLASS CLASS CLASS CLASS NO. ACTIVITY A B C D 13 Provide Design Control Over the Fo!!owing Documents:

• P & lD S S S S

• Pipe Support Drewings W W W W l3

• Provide Construction and As-Built Piping Isometrics C C C C

• Pipe Whip Restraint Drawings W W W W 3 14 Provide data base of X developed W W W W PAGES computer base Piping Models and load input in the input fermat of 3 the S&L computer progran PIPSYS based on PIPSYS user manual Revision 5, April 1982.

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APPENDIX 2 BASE LINE DDCUMENT The P & ID Drawing prepared by Sargent & Lundy serves as the record of interf aces for the Byron plant Auxiliary Building. By means of appropriate color coding and affixation of serialized numbers, the work scope for piping analysis and supports design of Sargent & Lundy, Westinghouse, and Nuclear Power Services (NPS) are Identified. Controlled copies of the P & ID's will be 3

maintained at the construction site by Sargent & Lundy under direction of Commenwealth construction. These copies will be maintained in real time to correspond with the progress of construction activities, analysis activites, and preparation of design drawings. For systems which contain shared scope, anchor locations (see next item) will be Identified on the P & ID with appropriate designation of responsibility on either side of the anchor.

ANCHOR LOCATIONS A sketch will be prepared by Westinghouse which specifies anchor locations at locations of scope / responsibility changes. These anchor location sketches will 3 Identify which organization is responsible at the anchor and in either direction extending away from the anchor. The anchor schematic diagrams will be serialized such that they are identified on the P & ID's (see above).

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APPENDIX 3 INTERFACE CENTROL AGREEMENT ADDENDUM SITE

1.0 INTRODUCTION

The purpose of this Interface document is to define the relationship between the Westinghouse Structural Analysis Mobile Unit (SAMU) design group and the Sargent & Lundy (S & L) Piping / Support / Analysis field group.

Either S & L or y SAMU may Interf ace with and/or perf orm design tasks for resolution of fleid problems in the other's scope of assigned subsystems.

The overall responsibility for the work performed will reside witt, the respective party presently assigned that subsystem.

This appendix supplements the Westinghouse - Commonwealth Edison Company -

Sargent & Lundy Interf ace Control Agreement.

2.0 SCOPE -

This interface Control Agreement Appendix applies to work activities between Westinghouse and Sargent & Lundy at the Byron Site. All design activities will be performed in accordance with the respective CECO approved y or S & L Q. A. program (s) and applicable procedures whica are discussed in Section 5.3 of this interf ace Control Agreement.

2.1 RESPONSIBILITIES 3

Fleid Problems will be received by the field group that is presently assigned that subsystem responsibility. The assignment of the field problems for resolution (re-design, calculations, analytical check), upon notification by CECO to S & L and Westinghouse SAMU, may be to either on-site work group. The specific assignment of which field problems to reassign shall reside with the site group presently assigned the subsystems having outstanding field problems. Reconciliation of out-of-tolerances will remain the responsibility of the group assigned the subsystem, i

l Appropriate design input information needed to resolve the field problems l will be provided with the problem or access to the Information will be made i

availab'e. (Proprietary information excluded.)

Cross-training will be provided in areas where differences in procedures and design requirements or methods exist. Documented records of ,

' cross-training and documentation of personnel qualification will be maintained by the respective parties. This documentation will be available for review.

All original design Information, including calculations resulting f rom the problem resolution, will be supplied to the responsible field group with the resolution. The responsible field group will maintain recorcs as required and will issue the revised hanger drawings.

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14 2.3 CELo RESPONSIBILITIES 1

Ceco will establish the completion priorities for subsystems'es the 3

, scheduling dictates and will monitor the work load for all Field Groups.

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APRIL 8, 1983 LETTER FROM A. STONE IS IN PREPARATION.

NPS DESIGN CONTROL PROCEDURE IS ATTACHED.

WORK PROCEDURE 3.0.4 i

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